ML20058N783
| ML20058N783 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/08/1993 |
| From: | Blough A Office of Nuclear Reactor Regulation |
| To: | Richard Anderson NORTHERN STATES POWER CO. |
| Shared Package | |
| ML20058N786 | List: |
| References | |
| GL-89-04, GL-89-4, TAC-M86807, TAC-M86808, NUDOCS 9312220262 | |
| Download: ML20058N783 (3) | |
Text
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UNITED STATES f
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WASHINGTON, D.C. 205GELonot
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Decrber 8,1993
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Docket Nos. 50-282 and 50-306 Mr. Roger 0. Anderson, Director Licensing and Management Issues Northern States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401
Dear Mr. Anderson:
SUBJECT:
APPROVAL OF THIRD 10-YEAR INSERVICE TESTING PROGRAM RELIEF REQUESTS FOR PUMPS AND VALVES - PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 (TAC NOS. M86807 AND M86808)
By letters dated June 16, 1993, and August 25, 1993, Northern States Power Company (NSP) submitted its Third 10-Year Inservice Testing (IST) Program for the Prairie Island Nuclear Generating Plant, Units 1 and 2.
The staff, with technical assistance from Brookhaven National Laboratory (BNL), has reviewed the information e: acerning the IST program, including the information provided in the letter frco NSP dated November 10, 1993, which contained information that NSP provided in response to BNL's questions. The third 10-year intervals begin December 16, 1993, and December 21, 1994, for Units 1 and 2, respectively.
The staff adopts the evaluations and recommendations for granting relief or authorizing alternatives contained in the attached Technical Evaluation Report (TER) prepared by BNL, as reflected or modified in the enclosed Safety l
Evaluation (SE). Relief is granted from or alternatives are authorized for the testing requirements which have been determined to be impractical to perform or where compliance would result in a hardship without a compensating increase in safety. The IST program was developed to the 1989 Edition of the ASME Boiler and Pressure Vessel Code (the Code), which references the ASME Operations and Maintenance (0M) Standards, Part 6 and Part 10, for IST of l
pumps and valves. The use of the 1989 Edition in this manner is approved pursuant to 10 CFR 50.55a(f)(4)(iv). The relief requests were reviewed l
against the requirements of ASME OM Part 6 and Part 10.
Interim approval is authorized for Relief Requests 1 and 2 for a period of 1 year or until the next refueling outage of each unit, whichever is later. The poH 40n of Relief Request 5 related to use of alternate acc.eptance criteria is denied. Authorization of Relief Request 10 is acceptable until the next refueling outage for each unit when NSP has committed to install flow instrumentation.
The IST program relief requests which are granted or authorized are acceptable for implementation provided the action items identified in Section 5 of the TER are addressed within 1 year of the date of the SE or by the end of the next refueling outage, whichever is later. Additionally, the granting of hg %Y 9312220262 93120s fDR ADDCK 0500 2
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Mr. Roger 0. Anderson Decenber 8, 1993 relief is based upon the fulfillment of any commitments made by NSP in its
' basis for each relief request and the alternatives proposed. A summary of the NRC actions is provided in Table 1 of the enclosed SE. The test deferrals for valves which are in accord with ASME OM Part 10 have been reviewed and are
!I summarized in Table 4.1 of the TER.
l I
Where interim relief has been granted, NSP should resolve the issues before expiration of the interim period. NSP should respond to the NRC within 1 year of the date of this SE describing actions taken, actions in progress, or actions to be taken, to address each of these items.
Program changes involving new or revised relief requests should not be implemented prior to approval by the NRC except as authorized by Generic Letter (GL) 89-04, " Guidance on Developing Acceptable Inservice Testing Programs." New or revised relief requests that meet the positions in GL 89-04, Attachment 1, should be submitted to the NRC but may be implemented provided the guidance in GL 89-04, Section D, is followed.
Program changes that add or delete components from the IST program should also be periodically submitted to the NRC.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, Original sigmd by L.N. 01shan FOR 23 A. Randolph Blough, Acting Director l
Project Directorate III-l Division of Reactor Projects -III/IV/V Office of Nuclear Reactor Regulation
Enclosures:
safety Evaluation, w/att. TER Report cc w/ enclosures:
See next page DISTRIBUTION Docket File NRC & Local FDRs PDIII-1 Reading T. Murley/F. Miraglia L. J. Callan, Acting E. Rossi J. Lieberman E. Jordan J. Roe, 13/E/4 J. Zwolinski,13/H/24 l
A. Blough C. Jamerson M. Gamberoni (2)
OGC-WF D. Hagan, 3206 MNBB G. Hill (4), PI-22 ACRS (10)
OPA OC/LFDCB B. McCabe, EDO 17/G/21 B. Jorgensen, R-III P. Campbell, EMEB LA:PD31k INT:PD31c PM:PD31 h OGCd / # (A)D:PD31 hf_0$
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l Mr. Roger 0. Anderson Dreter 8,193 relief is based upon the fulfillment of any commitments made by NSP in its basis for each relief request and the alternatives proposed. A summary of the NRC actions is provided in Table 1 of the enclosed SE. The test deferrals for valves which are in accord with ASME OM Part 10 have been reviewed and are summarized in Table 4.1 of the TER.
Where interim relief has been granted, NSP should resolve the issues before expiration of the interim period. NSP should respond to the NRC within 1 year of the date of this SE describing actions taken, actions in progress, or actions to be taken, to address each of these items.
Program changes involving new or revised relief requests should not be implemented prior to approval by the NRC except as authorized by Generit Letter (GL) 89-04, " Guidance on Developing Acceptable Inservice Testing Programs." New or revised relief requests that meet the positions in GL 89-04, Attachment 1, should be submitted to the NRC but may be implemented provided the guidance in GL 89-04, Section D, is followed.
Program changes that add or delete components from the IST program should also be periodically submitted to the NRC.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, Original signed by L.N. Olshan FOR A. Randolph Blough, Acting Director Project Directorate III-I Division of Reactor Projects -III/IV/V Office of Nuclear Reactor Regulation
Enclosures:
Safety Evaluation, w/att. TER Report cc w/ enclosures:
See next page QISTRIBUTION Docket File NRC & Local PDRs PDIII-I Reading T. Murley/F. Miraglia L. J. Callan, Acting E. Rossi J. Lieberman E. Jordan J. Roe, 13/E/4 J. Zwolinski,13/H/24 A. Blough C. Jamerson l
M. Gamberoni (2)
OGC-WF j
D. Hagan, 3206 MNBB G. Hill (4), PI-22 i
ACRS (10)
OPA OC/LFDCB B. McCabe, EDO 17/G/21 B. Jorgensen, R-III P. Campbell, EMEB LA:PD31k INT:PD31c PM:PD31 h OGCd/, (A)D:PD31 DFFICE CJamerscMCBajwa:N MGamberoY
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Mr.' Roger 0. Anderson, Director Prairie Island Nuclear Generating
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Northern States Power Company Plant cc:
J. E. Silberg, Esquire 1
l Shaw, Pittman, Potts and Trowbridge j
2300 N Street, N. W.
Washington DC 20037 d
Mr. E. L. Watzl, Site General Manager Prairie Island Nuclear Generating Plant Northern States Power Company 1717 Wakonade Drive East Welch, Minnesota 55089
]
Lisa R. Tiegel Assistant Attorney General Environmental Protection Division Suite 200 520 Lafayette Road St. Paul, Minnesota 55155 U.S. Nuclear Regulatory Commission
)
Resident In';pector Office 1719 Wakonade Drive East Welch, Minnesota 55089-9642 i
Regional Ad.ninistt stor, Region III U.S. Nuclear Regulatory Commission
(
799 Roosevelt Road i
Glen Ellyn, Illinois 60137 I
Mr. Jeff Cole, Auditor / Treasurer j
Goodhue County Courthouse i
Box 408 Red Wing,
.nnesota 55066-0408 Kris Sanda. Cctmissioner Department of Public Service 121 Seventh Place East Suite 200 St. Paul, Minnesota 55101-2145 Odober 1993 l